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Analysis of Beyond Design Nuclear Events
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Analysis of Beyond Design Nuclear Events
Analysis of Beyond Design Nuclear Events
Fuel Performance Codes
Multi Physics Codes
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Analysis of Beyond Design Nuclear Events
Multi Physics Codes
Multi Physics Codes
ERANOS
C4P-TRAIN
COUPLE
KORIGEN
PARTISN
SIMMER
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Safety Analysis of ADS
Facility Design, System Dynamics and Safety
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Facility Design, System Dynamics and Safety
Facility Design, System Dynamics and Safety
Experiments and Analyses
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Facility Design, System Dynamics and Safety
Experiments and Analyses
Experiments and Analyses
KASOLA
SOLTEC 1-3
ATEFA
DITEFA
Renewable Energies
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Facility Design, System Dynamics and Safety
Renewable Energies
Renewable Energies
AMTEC
CSP
Sodium
Thermocline
Fusion
Nuclear Safety
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Facility Design, System Dynamics and Safety
Nuclear Safety
Nuclear Safety
Safety Analyses of SFR
Sodium aerosol behaviour with CONTAIN-LMR code
Liquid Metal Fluid-dynamics and Effect on Materials
EU Framework Projects
ESFR-SMART
Codes
Basic Research
LIMCKA
Design and Analyses of nuclear Components
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Design and Analyses of nuclear Components
Design and Analyses of nuclear Components
Design and Analyses
Qualification of Fabrication Technologies
Numerical modelling and experimental validation
Financial, Personal and Cross-section Tasks
Complex Experiments, Experimental Design
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Complex Experiments, Experimental Design
Complex Experiments, Experimental Design
HELOKA
Measurement Technology and Experimental Methods
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Measurement Technology and Experimental Methods
Measurement Technology and Experimental Methods
Experimental Facilities
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Measurement Technology and Experimental Methods
Experimental Facilities
Experimental Facilities
L-STAR
Cooling Gas Chemistry
Magnet Safety
Minichannel Gas Cooling
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Measurement Technology and Experimental Methods
Minichannel Gas Cooling
Minichannel Gas Cooling
Pressure Drop and Heat Transfer
Flow Velocity Profile
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Design of Irradiation Experiments
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Measurement Technology and Experimental Methods
Design of Irradiation Experiments
Design of Irradiation Experiments
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Neutronics and Nuclear Data
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Neutronics and Nuclear Data
Neutronics and Nuclear Data
Nuclear Data for Fusion Technology
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Neutronics and Nuclear Data
Nuclear Data for Fusion Technology
Nuclear Data for Fusion Technology
Simulation Codes
Neutronic Experiments and Computational Analyses
Methods and Computational Tools
Nuclear Design Analyses
Neutronics for IFMIF
TALYS-G code
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Neutronics and Nuclear Data
TALYS-G code
TALYS-G code
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Reactor Physics and Dynamic
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Reactor Physics and Dynamic
Reactor Physics and Dynamic
Core thermal hydraulic Analysis Methods
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Reactor Physics and Dynamic
Core thermal hydraulic Analysis Methods
Core thermal hydraulic Analysis Methods
The subchannel thermal hydraulic code SubChanFlow
The Porous Media Two-phase Flow Code TwoPorFlow
Multiscale Methods for Reactor Safety
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Reactor Physics and Dynamic
Multiscale Methods for Reactor Safety
Multiscale Methods for Reactor Safety
Mutiscale Coupling of System Thermal Hydraulic with a Subchannel Codes
Multiscale Coupling of System Thermal Hydraulic with CFD-Codes
Core Neutronics Methods and Codes
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Reactor Physics and Dynamic
Core Neutronics Methods and Codes
Core Neutronics Methods and Codes
The finite element, parallel PN-transport solver based on domain-decomposition PARAFISH
PIRS Reactor Simulation Package
Multiphysics Methods for Improved Safety Evaluations of Reactor Systems
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Reactor Physics and Dynamic
Multiphysics Methods for Improved Safety Evaluations of Reactor Systems
Multiphysics Methods for Improved Safety Evaluations of Reactor Systems
Neutronic / Thermal Hydraulic/ Thermo-mechanics Coupled codes Based on Nodal Diffusion Solvers
Neutronic / Thermal Hydraulic Coupled codes Based on SP3-Transport Solvers
High fidelity Multiphysics based on Monte Carlo /SubChannel Codes
Methods and Codes for the Analysis of Design Basis Accidents
Methods and Codes for the Safety Analysis of Severe Accidents
Uncertainty and Sensitivity Analysis Codes
RPD Projects
Thermal-hydraulic Simulations and Optimization
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